IR 05000336/1999001
| ML20205D351 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/29/1999 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20205D328 | List: |
| References | |
| 50-336-99-01, 50-336-99-1, NUDOCS 9904020171 | |
| Download: ML20205D351 (48) | |
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.1 U. S.~ NUCLEAR REGULATORY COMMISSION
. REGION I Docket No.
50-336 License No.
DPR-65 Report No.
50-336/99-01 Licensee:
Northeast Nuclear Energy Company Facility:
Millstone Unit 2 Dates:
January 19 through February 17,1999 Inspectors:
W. Cook, Team Leader, DRP L. Prividy, Assistant Team Leader, DRS P. Cataldo, DRP -
G. Cranston, DRS L. James, DRS S. Jones, DRP W. Maier, DRS D. Beckman, Contractor Approved By:
James C. Linville, Chief
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Projects Branch 6 Division of Reactor Projects
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9904020171 990 2 PDR ADOCK 05000336
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EXECUTIVE SUMMARY Millstone Unit 2 NRC Inspection Report 50-336/99-01 During thr weeks of January 19 and February 1,1999, a team of inspectors conducted an onsite inspection of the licensee's corrective action program implementation using the guidance of NHC Inspection Procedure 40500, " Effectiveness of Licensee Controls in identifying,
' Resolving, and Preventing Problems." The results of this inspection were summarized at a public exit meeting conducted on February 17,1999 at the Millstone Nuclear Power Station Training Center.
The team concluded that overall problem identification and processing by the Condition Report
. process was generally good, with a low threshold and high volume input to the process.
Assignment of significance level and initial screening was appropriate. Root cause evaluation and corrective action development and implementation were generally good. A few instances were identified where the extent of condition reviews were tor narrowly focused.
No system hardware discrepancies or operating concems were noted that were not previously identified by the licensee. The teem found the Condition Report use was generally acceptable.
System Engineers were very knowledgeable of their systems, were conversant with past and
. present operability concems and knew the status of their system's readiness for restart.
Additionally, the System Engineers were knowledgeable and conversant with the Corrective-Action Program and utilized the program effectively to identify and to track problems associated with their systems.. The team noted that the material condition of the four selected systems was good, as was the portion of the plant observed during the walkdown of each of the four systems.
Based upon the team's limited review of Maintenance Rule implementation, the licensee was
- effectively utilizing trend analysis to identify maintenance related system performance problems.
The team identified that licensee identification and tracking of control room deficiencies was generally good. However, the licensee failed to initiate Condition Reports in accordance with station procedure RP 4, " Corrective Action Program," for the proper evaluation of conditions adverse to quality involving the charging pump hand switches and reactor building closed cooling water system valve 2-RB-210 leakage. This Severity Level IV violation of procedural requirements is being treated as a Non-Cited Violation, consistent with Appendix C of the NRO Enforcement Policy. The team acknowledged that other tracking systems were used to ensure final resolution of these control room deficiencies, but these tracking mechanisms lacked appropriate operability reviews to assess system or plant impact. (NCV 50-336/99-01-01)
The team concluded that, in spite of minor administrative deficiencies, the operability determination process and associated corrective actions were aapropriate for the affected structures, systems, and components important to safety. The licensee was properly identifying problems associated with plant safety systems and adequately implementing temporary modifications, where warranted. However, all of the temporary modifications had been installed longer than the six months procedural limit indicating poor administrative control and management oversigh' :f this activity.
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The team concluded thet the licensee had adequately identified and scheduled training for operators in preparation for the plant restart. Additionally, action items relating to the lessons leamed from the Unit 3 restart were being adequately tracked and incorporated into the licensed and non-licensed operator training cycle.
The team considered the licensee's Human Performance Enhancement System (HPES)
program to be a contribution to error prevention. This contribution was primarily manifested in
the education and indoctrination efforts of the HPES newsletters and the actions of the HPES committees.
The team concluded that the Action item Tracking and Trending System (AITTS) was a powerful tool being used by plant staff, managers, and oversight organi?ations to ensure appropriate tracking of corrective action assignments and that AITTS was an effective trend analysis data base. The team found that the Corrective Action department adequately performs the trend analysis on a monthly and quarterly basis. Based upon a review of available trend data and discussions with Unit 2 management, it was evident to the team that the licensee was cognizant of the corrective action assignment backlog and that a well established prioritization plan was being used to help facilitate an appropriate work-off of the approximate 3500 backlogged work activities.
The team concluded that the Operations department self-assessment process was comprehensive, and adequately contributed to problem identification and resolution. In addition, the Work Observation program appeared to be an effective tool for the communication and improvement of standards and quality of performance within the Operations department. The
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team concluded that the Maintenance, Engineering, Plant Support, and Nuclear Oversight area
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self assessments were generally self-critical of the current work processes; were effective in identifying program and process enhancements; and were generally conducted consistent with the self-assessment guidelines.
Unit 2 Plant Operations Review Committee was conducted with appropriate regard to safety and good oversight of plant activities. Between the Station Operations Review Committee and Station Management Review Team activities, the licensee had an appropriate safety focus for cocective action matters of site-wide activities.
l The Nuclear Safety Assessment Board (NSAB) meets Technical Specification requirements for member qualifications and meetings. The board was providing effective oversight on impcrtant activities at Unit 2 as it prepared for plant rer, tart. A good initiative was observed regarding NSAB member participation in several System Readiness Reviews.
The Nuclear Oversight Verification Plan (NOVP) was a widely accepted method in use for continuous assessment of " key issues" important to support Unit 2 restart. The team viewed the NOVP as another good performance trending tool being effectively used by the plant staff and management.
Audits have been appropriately performed, such as the Fire Preiection audit, which was a valuable contribution to the assessment of this key issue in the NOVP. The Performance Evaluation group was "in touch" with the line organization activities and appeared to be in a iii
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good position for real time assessments of the line organi::ation performance. This group also provided current performance information from surveillances for inclusion in several " key issues" areas of the NOVP. The Recovery Oversight group was providing good technical and independent assessments in the Engineering and specialty areas, such as motor-operated valves and environmental equipment qualification programs, for inclusion in the NOVP. In summary, the team concluded that tha Nuclear Oversight organization was providing effective independent oversight of Unit 2 activities.
The team concluded that the Employee Concern Program was an effective vehicle for the acceptance and processing of safety issues identified to the Program.
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- SUMMARY Meetings were held periodically with licensee management during this inspection to discuss inspection observations and findings. A summary of preliminary findings was also discussed at the conclusion of the on-site inspection on February 5,1999. A public meeting was held on February 17,1999 at the Millstone Training Center to discuss the e
. team's findings and conclusions. The slides used at that public meeting are included as Attachment 1 to this repor r
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PARTIAL LIST OF PERSONS CONTACTED L. Olivier Sr. VP and CNO Millstone M. Brothers VP Nuclear Operations D. Amerine VP Engineering Services R. Necci VP Nuclear Oversight and Regulatory Affairs S.Sace Director Nuclear Oversight B. Wilkens Director Design Engineering P. Grossman.
Director Plant Engineering M. Bowling Recovery Officer S. Heard Manager, independent Review Team A. Price Director, Unit 2 H. Miller Manager, Regulatory Affairs J. Gionet Regulatory Affairs E. Annino Regulatory Affairs INSPECTION PROCEDURES USED IP 40500 Effectiveness of Licensee Controls for Identifying, Resolving, and Preventing Problems IP 71707 Plant Operations IP 92901-Follow-up - Operations ITEMS OPENED, CLOSED, AND DISCUSSED Opened / Closed NCV 50-336/99-01-01 Severity Level IV, Non-Cited violation involving failure to initiate Condition Reports for two control room deficiencies.
Go19d eel 50-336/96-201-30, Failure to implement timely corrective action for significant conditions adverse to quality.
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Discussed I
SIL No.1 Management Oversight and Effectiveness SIL No.11 Nuclear Oversight Program Effectivenass i
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LIST OF ACRONYMS USED ACRS Adverse Condition Reports AITTS Action l tem Tracking and Trending System AFW auxiliary feedwaier AR Action Request AWO automated work order CR-Condition Reports DBA designed basis accident EA Engineering Assurance ECP Employee Concerns Program EDG emergency diesel generators EEQ environmental equipment qualification EP Emergency Preparedness -
HPSI High Pressure Safety injection HPES Human Performance Enhancement System MDMRT multi-disciplinary management review team MOV motor-operated valves NCV Non-Cited Violation NO Nuclear Overtight NOSG Nuclear Oversight Surveillance Guides NOVP The Nuclear Oversight Verification Plan NSAB The Nuclear Safety Assessment Board NU Northeast Utilities OD operability determinations ODI Operations Departments Instruction PM preventive maintenance PORC Plant Operations Review Committee PTL pull-to-lock QRB Quality Review Board RBCC Reactor Closed Cooling Water SORC Station Operations Review Committee SW Service Water
' TAR Trend Analysis Reports TM temporary modifications TR trouble report TS Technical Specifications l
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